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WO2006025975A1 - Procede de separation entre l'yttrium-90 et le strontium-90 et de purification d'yttrium-90 - Google Patents

Procede de separation entre l'yttrium-90 et le strontium-90 et de purification d'yttrium-90 Download PDF

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Publication number
WO2006025975A1
WO2006025975A1 PCT/US2005/026247 US2005026247W WO2006025975A1 WO 2006025975 A1 WO2006025975 A1 WO 2006025975A1 US 2005026247 W US2005026247 W US 2005026247W WO 2006025975 A1 WO2006025975 A1 WO 2006025975A1
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solution
strontium
purified
solids
nitrate
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PCT/US2005/026247
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English (en)
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Lane Allan Bray
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Isoray Medical, Inc.
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Publication of WO2006025975A1 publication Critical patent/WO2006025975A1/fr

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    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21F—PROTECTION AGAINST X-RADIATION, GAMMA RADIATION, CORPUSCULAR RADIATION OR PARTICLE BOMBARDMENT; TREATING RADIOACTIVELY CONTAMINATED MATERIAL; DECONTAMINATION ARRANGEMENTS THEREFOR
    • G21F9/00—Treating radioactively contaminated material; Decontamination arrangements therefor
    • G21F9/04—Treating liquids
    • G21F9/06—Processing
    • G21F9/08—Processing by evaporation; by distillation
    • C—CHEMISTRY; METALLURGY
    • C01—INORGANIC CHEMISTRY
    • C01F—COMPOUNDS OF THE METALS BERYLLIUM, MAGNESIUM, ALUMINIUM, CALCIUM, STRONTIUM, BARIUM, RADIUM, THORIUM, OR OF THE RARE-EARTH METALS
    • C01F11/00—Compounds of calcium, strontium, or barium
    • C01F11/36—Nitrates
    • C—CHEMISTRY; METALLURGY
    • C01—INORGANIC CHEMISTRY
    • C01F—COMPOUNDS OF THE METALS BERYLLIUM, MAGNESIUM, ALUMINIUM, CALCIUM, STRONTIUM, BARIUM, RADIUM, THORIUM, OR OF THE RARE-EARTH METALS
    • C01F17/00—Compounds of rare earth metals
    • C01F17/20—Compounds containing only rare earth metals as the metal element
    • C01F17/276—Nitrates
    • C—CHEMISTRY; METALLURGY
    • C22—METALLURGY; FERROUS OR NON-FERROUS ALLOYS; TREATMENT OF ALLOYS OR NON-FERROUS METALS
    • C22B—PRODUCTION AND REFINING OF METALS; PRETREATMENT OF RAW MATERIALS
    • C22B3/00—Extraction of metal compounds from ores or concentrates by wet processes
    • C22B3/04—Extraction of metal compounds from ores or concentrates by wet processes by leaching
    • C22B3/06—Extraction of metal compounds from ores or concentrates by wet processes by leaching in inorganic acid solutions, e.g. with acids generated in situ; in inorganic salt solutions other than ammonium salt solutions
    • C22B3/065—Nitric acids or salts thereof
    • C—CHEMISTRY; METALLURGY
    • C22—METALLURGY; FERROUS OR NON-FERROUS ALLOYS; TREATMENT OF ALLOYS OR NON-FERROUS METALS
    • C22B—PRODUCTION AND REFINING OF METALS; PRETREATMENT OF RAW MATERIALS
    • C22B3/00—Extraction of metal compounds from ores or concentrates by wet processes
    • C22B3/20—Treatment or purification of solutions, e.g. obtained by leaching
    • C22B3/44—Treatment or purification of solutions, e.g. obtained by leaching by chemical processes
    • C—CHEMISTRY; METALLURGY
    • C22—METALLURGY; FERROUS OR NON-FERROUS ALLOYS; TREATMENT OF ALLOYS OR NON-FERROUS METALS
    • C22B—PRODUCTION AND REFINING OF METALS; PRETREATMENT OF RAW MATERIALS
    • C22B59/00—Obtaining rare earth metals
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21G—CONVERSION OF CHEMICAL ELEMENTS; RADIOACTIVE SOURCES
    • G21G4/00—Radioactive sources
    • G21G4/04—Radioactive sources other than neutron sources
    • G21G4/06—Radioactive sources other than neutron sources characterised by constructional features
    • G21G4/08—Radioactive sources other than neutron sources characterised by constructional features specially adapted for medical application
    • C—CHEMISTRY; METALLURGY
    • C01—INORGANIC CHEMISTRY
    • C01P—INDEXING SCHEME RELATING TO STRUCTURAL AND PHYSICAL ASPECTS OF SOLID INORGANIC COMPOUNDS
    • C01P2006/00—Physical properties of inorganic compounds
    • C01P2006/88—Isotope composition differing from the natural occurrence
    • C—CHEMISTRY; METALLURGY
    • C22—METALLURGY; FERROUS OR NON-FERROUS ALLOYS; TREATMENT OF ALLOYS OR NON-FERROUS METALS
    • C22B—PRODUCTION AND REFINING OF METALS; PRETREATMENT OF RAW MATERIALS
    • C22B26/00—Obtaining alkali, alkaline earth metals or magnesium
    • C22B26/20—Obtaining alkaline earth metals or magnesium
    • Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
    • Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02P—CLIMATE CHANGE MITIGATION TECHNOLOGIES IN THE PRODUCTION OR PROCESSING OF GOODS
    • Y02P10/00—Technologies related to metal processing
    • Y02P10/20—Recycling

Definitions

  • Y-90 Yttrium-90
  • Sr-90 Strontium-90
  • Uses of the Y-90 purified by the method include cancer research and treatment, such as for use in cell directed therapy.
  • Radiotherapy refers to the treatment of diseases, including primarily the treatment of tumors such as cancer, with radiation. Radiotherapy is used to destroy malignant or unwanted tissue without causing excessive damage to the nearby healthy tissues.
  • Ionizing radiation can be used to selectively destroy cancerous cells contained within healthy tissue. Malignant cells are normally more sensitive to radiation than healthy cells. Therefore, by applying radiation of the correct amount over the ideal time period, it is possible to destroy all of the undesired cancer cells while saving or minimizing damage to the healthy tissue. For many decades, localized cancer has often been cured by the application of a carefully determined quantity of ionizing radiation during an appropriate period of time. Various methods have been developed for irradiating cancerous tissue while minimizing damage to the nearby healthy tissue. Such methods include the use of high-energy radiation beams from linear accelerators and other devices designed for use in external beam radiotherapy. Another method of radiotherapy includes cell directed therapy.
  • a targeting molecule which is a binding partner of a molecule on a cancer cell, is radiolabeled.
  • targeting molecules include antibodies, e.g., monoclonal antibodies.
  • the targeting molecule may be radiolabeled directly or indirectly via another molecule (e.g., chelating compound) that binds a radionuclide and is attached to the targeting molecule.
  • Yttrium-90 (Y-90) with a half-life of 64 hours is finding an increasing use in the treatment of various forms of cancer.
  • NCI National Cancer Institute
  • Y-90 is the cancer- killing isotope used in the first FDA approved radiopharmaceutical used in cell directed therapy, with a specific use for the treatment of non-Hodgkin's Lymphoma.
  • Y-90 a beta emitter, has important properties and is expected to be similarly used for many forms of cancer treatment.
  • Y-90 With the increasing demand for Y-90, there is a need for a method capable of producing multi-curie quantities of Y-90 on a weekly basis.
  • the Y- 90 must be chemically and radio chemically pure.
  • Sr-90/Y-90 separation factors less than 1x10 "6 (and preferably less than 1x10 "8 ) are required in order to reduce human exposure to long-lived Sr-90.
  • numerous metal cations e.g., iron, nickel, zirconium, etc.
  • Yttrium-90 is produced by radioactive decay of Sr-90.
  • a primary U.S. source of Y-90 is found in the nuclear fission product waste containing Sr- 90, stored in highly radioactive waste tanks at the Hanford nuclear site near Richland, WA.
  • a representation of the in-growth of Y-90 from 3.5 Ci of Sr-90 as a function of time (assuming the original 3.5 Ci of Sr-90 is void of Y-90) is shown in Figure 1. It requires between 14 and 21 days to come to equilibrium. To separate the Y-90, the Sr-90 target is "milked" multiple times over selected intervals, such as 14 days in which over 95% of the Y-90 is available, as depicted in Figure 2.
  • the separated Y-90 In order to be useful, the separated Y-90 must be exceptionally pure, free from other metal ions and free from Sr-90, an extremely toxic bone- seeking isotope.
  • the typical therapeutic dose of Y-90 labeled monoclonal antibodies is in the range of 100-300 millicuries of Y-90 per patient. Since an antibody is modified to contain only one molecule of chelating ligand per molecule of immunoprotein within the antibody, the total binding sites for metal ions are limited to about 7x10 9 moles on 1 mg of chelate-modified immunoprotein. Since complexes of several metal ions including zirconium (IV) and iron (III) form much stronger bonds than Y-90, specifications for chemical purity of Y-90 are necessarily strict for efficient labeling.
  • the Y-90 is formed by the decay of Sr-90 with a 30-year half-life. Y-90 decays with a 68-hour half-life to form non-radioactive zirconium (Zr). Even if the Sr-90 starting feed is free from other metallic impurities, Zr (IV) will continue to build up in the cow and will require separation from the purified Y- 90.
  • the present invention discloses a method of producing and purifying Y-90.
  • the present invention provides a method to semi-continuously milk the Y-90 from a Sr-90 "cow".
  • the method provides purified Y-90, removes any traces of Sr-90 and Zr decay product, and converts the purified Y-90 to a suitable form (e.g., dilute hydrochloric acid), for example for cancer research and treatment.
  • a unique chemical method of separation for Zr is disclosed herein and provides a zirconium clean-up step for the Y-90.
  • the method for purifying Y-90 from Sr-90 comprises the steps of:
  • the strontium nitrate salt in step (a) is a strontium salt other than nitrate that has been converted to strontium nitrate by the use of HNO 3 .
  • steps (c) and (d) are repeated with the solids of step (d) and the acid solution from each step (d) is combined.
  • the acid solution of step (d) is evaporated to incipient dryness and steps (c) and (d) are repeated.
  • the method has additional step (e), comprising (e) contacting the acid solution of step (d) containing the Y-90 with a resin that removes strontium, thereby removing trace strontium if present from the Y-90.
  • the method has additional steps (e) and (T), comprising (e) replacing the HNO 3 in the acid solution of step (d) containing the Y-90, with HCI; and (f) contacting the HCI acid solution containing the Y-90 with a resin that removes zirconium, thereby removing zirconium if present from the Y-90.
  • the method has additional steps (e) and (T), comprising (e) evaporating the solution containing the purified Y-90 to incipient dryness; and (f) dissolving the purified Y-90 with a solution of choice.
  • the method comprises the steps of dissolving the strontium nitrate "cow" comprised of Sr, Sr-90, Y-90 from the decay of Sr- 90, and zirconium (Zr) from the decay of Y-90, in a water solution, evaporating the solution to incipient dryness, contacting the crystalline solids with greater than 80% to about 90-wt% (preferably about 85-90-wt% or at least 85-wt%) HNO3 to precipitate the Sr as Sr(NO3)2. separating the solids from the acid solution containing the Y-90, and evaporating the solution to remove the acid from the Y-90 final purified product.
  • Addition of a second, much smaller volume of 85-90-wt% or at least 85-wt% HNO3, followed by a second solid-liquid separation is an optional step.
  • the acid solution may be passed through a small Sr-selective membrane (e.g., 3M Sr Rad disk) in the nitrate form.
  • the Y-90 final purified product is evaporated to dryness and brought up in an acid solution for analysis and shipment, usually hydrochloric acid. If Zr is present in the final Y-90 product HNO 3 solution, the solution is converted to the HCI form and passed through a small anion exchange resin membrane to remove Zr(IV).
  • the HCI acid solution may be passed through a small Sr-selective membrane (e.g., 3M Sr Rad disk).
  • the final Y-90 chloride solution is taken to dryness to remove the concentrated HCI.
  • the purified Y-90 free of Sr-90, Zr and other unwanted ions is dissolved in dilute HCI or other acid as specified by the end user.
  • the Sr(N 03)2 "cow" can be "remilked” as additional Y-90 becomes available from the decay of Sr-90.
  • Figure 1 entitled “In-Growth of Y-90 from the decay of Sr-90", is a diagram of the theoretical in-growth of Y-90 during 56-days, by Sr-90 decay after separation.
  • Figure 2 entitled “Simulated 'Milking' of Sr-90 for Y-90, 14-Day
  • Cycle is a diagram of the buildup of Y-90 using a 14-day milking cycle, with the decay of Sr-90.
  • Figure 3 entitled "Simulated 'Milking' of Sr-90 for Y-90, 7-Day Cycle", is a diagram of the buildup of Y-90 using a 7-day milking cycle, with the decay of Sr-90.
  • Figure 4 entitled “Sr/Y Separations Process Flow Diagram”, is a process flow diagram depicting the preferred embodiment of the process steps.
  • Figure 5 entitled “Fractional Recovery of Sr, Y and Zr as a Function of Nitric Acid Concentration", is a diagram of the fractional recovery of Sr 1 Zr and Y as a function of the Wt % nitric acid.
  • Figure 6 entitled "Concentration ( ⁇ g/mL) of Sr, Y and Zr as a Function of Nitric Acid Concentration", is a diagram of the Sr, Zr and Y mass solubility ( ⁇ g/mL) as a function of the Wt % nitric acid.
  • the present invention provides a method of separating and purifying Y-90 from Sr-90.
  • the method is efficient and economical.
  • the impurities removed, including Zr, are not returned to the original Sr-90 source.
  • the impurities do not continue to build up in the "cow.”
  • Sr-90 since Sr-90 is expensive, it is important to recover it for further use.
  • the trace of Sr (if present) in the separated Y-90 is removed. Y-90 preparations of purity heretofore unavailable are produced.
  • nitric acid concentrations from greater than 80-wt% to at least about 90-wt% are useful to separate and purify Y-90 from Sr-90. Further unexpectedly the solubility of Sr continues to decrease as the concentration of nitric acid continues to increase to about 90-wt%, rather than the minimum solubility of Sr being reached at a lower concentration of nitric acid.
  • a concentration of nitric acid in the range typically from greater than 80-wt% to about 90-wt% may be used, with a range of at least 85-wt% or about 85-90-wt% being preferred.
  • the concentration of the nitric acid is at least 90-wt%. Any ranges disclosed herein include all whole integer ranges thereof (e.g., 85-90-wt% includes 85-89-wt%, 86-90-wt%, 86-89-wt%, etc.). If the nitric acid solution contains more than 86-wt% nitric acid, it is referred to as fuming nitric acid.
  • the initial Sr-90 "cow” may be in the form of SrCOjor other familiar forms, e.g., strontium nitrate or a strontium salt other than nitrate.
  • SrCO3 for example, is readily converted to Sr(NO3)2 by the addition of stoichiometric quantities of HNO3.
  • Sr(NO 3 ) 2 as the form of the initial Sr-90 "cow" or formed by conversion of a strontium salt other than nitrate to Sr(NO 3 ) 2 as the Sr-90 "cow" is the starting material for the method of the present invention.
  • Sr-90 may be in a solid or liquid form of Sr(NO3)2.
  • Sr(NO 3 ⁇ as the Sr-90 "cow" for the method of the present invention.
  • Sr(NO 3 ⁇ there are a variety of ways to obtain Sr(NO 3 ⁇ as the Sr-90 "cow" for the method of the present invention.
  • the isotopic composition of the Sr found is assumed to be approximately 20-wt% Sr-90 and therefore there are 0.038 g of total Sr per Ci of Sr-90.
  • the gram ratio of total Sr to Y is approximate 21 ,000.
  • the 3M EmporeTM anion exchange SR extraction disk and the 3M EmporeTM Sr Rad disks are uniquely suitable for removal of Zr and for removal of trace Sr, respectively, and useful for a preferred embodiment of this invention.
  • the disks are prepared and sold by 3M, St. Paul, MN, and consist of a paper thin membrane containing either an anion exchange resin or cation exchange resin, incorporated into a disk or cartridge, and can be designed to be placed on a syringe barrel.
  • the 3M EmporeTM extraction disks for the removal of trace Sr and Zr are an effective alternative to conventional radiochemical sample preparation methods that use wet chemistry or packed ion exchange columns.
  • the exchange absorbing resin is ground to a very fine high- surface area powder and "is secured in a thin membrane as densely packed, element-selective particles held in a stable inert matrix of PTFE
  • the solution containing the unwanted ion is passed through the paper thin extraction disk by placing the solution in a syringe barrel and forcing the solution through the disk with a plunger.
  • the method takes from 10 seconds to 1 minute to complete.
  • a second method is to place the extraction disk on a fritted or porous filter and forcing the solution through the disk by vacuum. The method is very fast and requires no ion exchange column system.
  • a "sandwich" (placing two different types of web together and accomplishing two different chemical separation tasks at the same time) may also be used.
  • the residual Sr nitrate "cow” is stored to allow in-growth of additional Y-90 in the crystal structure of the Sr nitrate solid, from the decay of Sr-90.
  • the Sr(NO3)2 solid is dissolved in water to release the Y-90(NO3)3.
  • the "Handbook of Chemistry and Physics", 31 st edition, 1949 lists the solubility of Sr(NO3)2 (211.65 g/mole) as "100g/100 ml_ H2O @ 90°C and 40.1g/100 ml_ H2O @ 0°C". Experimental tests have verified these solubility values.
  • Y-90 is useful for radiotherapy (such as to treat malignancies).
  • a radioactive substance e.g., Y-90
  • Y-90 may be used as part of the production of conjugates wherein a targeting molecule is radiolabeled with Y-90 for targeted delivery of the Y-90 to tumor cells.
  • the Y-90 may be bound to a chelating compound (to form a chelate) either before or after attachment of the chelating compound (or chelate) to the targeting molecule.
  • targeting molecules include antibodies, such as monoclonal antibodies. The method of the present invention provides purified Y-90 for these and other uses.
  • a preferred embodiment method of separation and purification of Y-90 is initially described with reference to Figure 4. It comprises the steps of 1 obtaining a quantity of Sr(NO3)2 containing Sr, Sr-90 and its decay products comprised of Y-90 and Zr formed by radioactive decay of Y-90.
  • the specific activity of Y-90 is -5.48x10 5 Curies (Ci) per gram of yttrium.
  • the nitric acid product 8 is passed through an ion exchange membrane filter (3M Sr Rad Disk). If the resulting Y-90 product 7 or 9 does not contain Zr, the Y(NU 3 ) 3 and HNO 3 are evaporated to incipient dryness 13 and redissolved in a dilute acid of choice 14 usually HCI as the final product 15. If the Y-90 meets specifications 7 but still contains Zr and traces of Sr-90, the nitric acid product solution is prepared for Zr removal 10.
  • the Y(NO3)3, Zr(NO3)4 plus HNO3 is evaporated 10 to incipient dryness to remove the acid.
  • the resulting solids are 11 dissolved in concentrated 12M HCI.
  • the YCI 3 solution 12 is passed through ion exchange membrane filters to remove Zr and any remaining traces of Sr-90.
  • the YCI 3 solution plus HCI is evaporated 13 to incipient dryness.
  • the purified Y-90 is dissolved 14 in dilute HCI as specified by the customer.
  • the Y-90 is certified 15 for shipment.
  • the Sr-90 "cow" is held in storage 16 to allow for in ⁇ growth of Y-90 and subsequent reuse.
  • the Sr, Y and Zr values found above in the aqueous filtrate were plotted as a function of their metal concentration in micrograms ( ⁇ g) found per milliliter (mL) of filtrate, Figure 6.
  • the results show that under the test conditions at less than 75-wt% acid the Sr concentration ( ⁇ g/mL) in solution is greater than Y ( ⁇ g/mL).
  • the two metal concentrations ( ⁇ g/mL) are approximately equal at ⁇ 78-wt% acid.
  • the Sr is less than Y.
  • the Y metal value is 14-times that of the Sr metal value.
  • Precondition with 12M HCI Precondition with 12M HCI. Pass 1 mL of Sr solution through the disk. Pass 1 mL of 12M HCI through the disk as a rinse. Submit 2 mL of the standard solution and 2 mL of the effluent for Sr 1 Zr, and Y for analysis.
  • a known weight of Sr(NO3) 2 representing a Sr-90 "cow” is dissolved in water to release the Y(NO3)3 and Zr(NO3)4 and taken to incipient dryness with a heat source.
  • An amount of 90-wt% HNO3 is added to the near dry Sr nitrate salt.
  • the majority of the Sr is precipitate based on its solubility as a function of the nitric acid concentration as Sr(NO3)2. while the Zr, Y, and traces of Sr nitrate remain in the HNO3 filtrate.
  • the Y, Zr and traces of Sr in the HNO3 filtrate are filtered or centrifuged to separate them from the Sr(NO3)2 salt.
  • the filtrate is evaporated to incipient dryness.
  • An amount of 90-wt% HNO3 approximately 1/1 Oth to 1/50th of that used above is added to the dried Y/Sr/Zr nitrate salts. The trace of remaining Sr will precipitate, while Zr and Y nitrate remain in the filtrate.
  • step #4 The resulting purified yttrium chloride solution is taken to dryness to remove any trace of nitrate that may have accompanied the dried nitrate salt (step #4), and then is taken up in a dilute acid solution (usually HCI) at the acid and radiochemical strength desired by the end user.
  • a dilute acid solution usually HCI
  • the resulting purified yttrium nitrate solution (6) is taken to dryness to remove any trace acid that may have accompanied the dried nitrate salt and then is taken up in a dilute acid solution (usually HCI) at the acid and radiochemical strength desired by the end user.
  • a dilute acid solution usually HCI
  • the Y-90 separation process was simulated using non-radioactive Sr(NO3)2 and standard solutions of Y(NO3)3 and Zr(NO3)4.
  • Two Sr "cow" concentrations along with varying the acid concentrations and volumes are shown below to demonstrate a variety of typical results, i.e. 3.5 Ci Sr-90 [0.34 g Sr(NO3)2] and 35 Ci Sr-90 [3.4 g Sr(NO3)2].

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Abstract

La présente invention concerne un procédé pour séparer et purifier l'yttrium 90 (Y-90) mélangé avec du strontium 90 (Sr-90). Un stade de purification de zirconium (Zr) est aussi prévu. L'utilisation d'Y-90 purifié par le procédé de l'invention concerne la recherche et le traitement en matière de cancer. Y-90 est particulièrement utile dans la thérapie cellulaire, par exemple, lorsque Y-90 est attaché directement ou indirectement à une molécule de ciblage telle qu'un anticorps.
PCT/US2005/026247 2004-07-26 2005-07-25 Procede de separation entre l'yttrium-90 et le strontium-90 et de purification d'yttrium-90 WO2006025975A1 (fr)

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US59136004P 2004-07-26 2004-07-26
US60/591,360 2004-07-26
US65366805P 2005-02-16 2005-02-16
US60/653,668 2005-02-16

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Families Citing this family (19)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
EP1766635B1 (fr) 2004-06-28 2008-03-26 Isoray Medical, Inc. Procede de separation et purification du cesium 131 a partir du nitrate de baryum
CA2576907C (fr) * 2004-07-28 2014-04-22 Isoray Medical, Inc. Procede de separation et de purification du cesium-131 a partir du carbonate de barium
US7316644B2 (en) * 2004-08-18 2008-01-08 Isoray Medical, Inc. Method for preparing particles of radioactive powder containing Cesium-131 for use in brachytherapy sources
US7510691B2 (en) * 2006-02-28 2009-03-31 Isoray Medical, Inc. Method for improving the recovery of cesium-131 from barium carbonate
BRPI0811938A2 (pt) 2007-05-21 2014-11-25 Exploration Orbite Vspa Inc Processos para a extração de alumínio e de ferro a partir de minérios aluminosos
KR100945020B1 (ko) * 2008-03-27 2010-03-05 한국원자력연구원 흡착제, 이의 제조방법 및 이를 이용한 스트론튬/이트륨발생기
AU2009264214B2 (en) 2008-06-24 2013-06-06 Technische Universitaet Muenchen Muteins of hNGAL and related proteins with affinity for a given target
BR112013023907A2 (pt) 2011-03-18 2019-09-24 Orbite Aluminae Inc processo de recuperação de ao menos um elemento terra-rara a partir de um material contendo alumínio
EP3141621A1 (fr) 2011-05-04 2017-03-15 Orbite Aluminae Inc. Procédés de récupération de terres rares dans divers minerais
EP2714594A4 (fr) 2011-06-03 2015-05-20 Orbite Aluminae Inc Procédés d'obtention d'hématite
IN2014DN03007A (fr) 2011-09-16 2015-05-08 Orbite Aluminae Inc
EP2802675B1 (fr) 2012-01-10 2020-03-11 Orbite Aluminae Inc. Procédés de traitement de boue rouge
CN104520237B (zh) 2012-03-29 2018-05-01 奥佰特氧化铝有限公司 处理飞灰的方法
RU2597096C2 (ru) 2012-07-12 2016-09-10 Орбит Алюминэ Инк. Способы получения оксида титана и различных других продуктов
US9353425B2 (en) 2012-09-26 2016-05-31 Orbite Technologies Inc. Processes for preparing alumina and magnesium chloride by HCl leaching of various materials
JP2016504251A (ja) 2012-11-14 2016-02-12 オーバイト アルミナ インコーポレイテッドＯｒｂｉｔｅ Ａｌｕｍｉｎａｅ Ｉｎｃ． アルミニウムイオンの精製方法
US9334549B2 (en) 2013-12-20 2016-05-10 General Electric Company Systems and methods for recovery of rare-earth constituents from environmental barrier coatings
US9409185B2 (en) 2014-04-17 2016-08-09 General Electric Company Systems and methods for recovery of rare-earth constituents from environmental barrier coatings
US20210238051A1 (en) * 2020-02-03 2021-08-05 Battelle Memorial Institute Systems and Methods for Separating Yttrium and Strontium

Citations (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US3706689A (en) * 1968-05-03 1972-12-19 Nuclear Associates Inc Process for the preparation of a sr**90-y**90 beta source in a radiation hazard free manner
US5368736A (en) * 1993-07-26 1994-11-29 The United States Of America As Represented By The United States Department Of Energy Process for the separation and purification of yttrium-90 for medical applications
WO2001080251A2 (fr) * 2000-04-14 2001-10-25 Pg Research Foundation, Inc. Procede d'isolation et de purification de 90y provenant de 90 strontium en quantites multi-curies

Family Cites Families (44)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US1753287A (en) 1925-05-15 1930-04-08 Failla Gioacchino Method and means for applying radium emanation
US3218123A (en) * 1962-11-23 1965-11-16 Jr Wallace Davis Recovery of strontium values from sulfate-containing waste solutions
US3351049A (en) 1965-04-12 1967-11-07 Hazleton Nuclear Science Corp Therapeutic metal seed containing within a radioactive isotope disposed on a carrier and method of manufacture
US3301789A (en) * 1966-03-04 1967-01-31 Lane A Bray Zirconium removal from strontium-90
US4323055A (en) 1980-04-08 1982-04-06 Minnesota Mining And Manufacturing Company Radioactive iodine seed
US4702228A (en) 1985-01-24 1987-10-27 Theragenics Corporation X-ray-emitting interstitial implants
JPH01254900A (ja) 1988-04-05 1989-10-11 Daiichi Radio Isotope Kenkyusho:Kk ガスターゲツト装置およびそれを用いたラジオアイソトープの製造方法
US4891165A (en) 1988-07-28 1990-01-02 Best Industries, Inc. Device and method for encapsulating radioactive materials
US4994013A (en) 1988-07-28 1991-02-19 Best Industries, Inc. Pellet for a radioactive seed
US5071610A (en) 1990-02-23 1991-12-10 Minnesota Mining And Manufacturing Company Method of making a controlled pore composite polytetrafluoroethylene
US5342283A (en) 1990-08-13 1994-08-30 Good Roger R Endocurietherapy
US6099457A (en) 1990-08-13 2000-08-08 Endotech, Inc. Endocurietherapy
US5154897A (en) * 1991-03-06 1992-10-13 University Of Missouri Method and apparatus for the generation of radioisotopes
US5225173A (en) * 1991-06-12 1993-07-06 Idaho Research Foundation, Inc. Methods and devices for the separation of radioactive rare earth metal isotopes from their alkaline earth metal precursors
US5512256A (en) 1992-05-08 1996-04-30 Battelle Memorial Institute Method of separation of yttrium-90 from strontium-90
US5405309A (en) 1993-04-28 1995-04-11 Theragenics Corporation X-ray emitting interstitial implants
US5494647A (en) * 1993-10-04 1996-02-27 The United States Of America As Represented By The United States Department Of Energy Use of Chelex-100 for selectively removing Y-90 from its parent Sr-90
US5683345A (en) 1994-10-27 1997-11-04 Novoste Corporation Method and apparatus for treating a desired area in the vascular system of a patient
US6458070B1 (en) 1994-10-27 2002-10-01 Novoste Corporation Method and apparatus for treating a desired area in the vascular system of a patient
US5899882A (en) 1994-10-27 1999-05-04 Novoste Corporation Catheter apparatus for radiation treatment of a desired area in the vascular system of a patient
US5591420A (en) 1995-08-25 1997-01-07 Battelle Memorial Institute Cesium titanium silicate and method of making
US6589502B1 (en) 1995-11-27 2003-07-08 International Brachytherapy S.A. Radioisotope dispersed in a matrix for brachytherapy
US5749042A (en) 1997-01-28 1998-05-05 Battelle Memorial Institute Bismuth generator method
US6139749A (en) 1997-11-20 2000-10-31 3M Innovative Properties Company Method for radioactive species analysis using a self-scintillating sheet material
US6060036A (en) 1998-02-09 2000-05-09 Implant Sciences Corporation Radioactive seed implants
CA2261338A1 (fr) 1998-02-12 1999-08-12 Robert Robertson Sources de curietherapie a faible energie encapsulees
DE19850203C1 (de) 1998-10-23 2000-05-31 Eurotope Entwicklungsgesellsch Radioaktive Jod-125-Seeds basierend auf Keramikträgern und Verfahren zur Herstellung dieser Seeds
US6689043B1 (en) 1998-11-06 2004-02-10 Amersham Plc Products and methods for brachytherapy
RU2251437C2 (ru) 1998-11-06 2005-05-10 Амершем пи-эл-си Радиоактивный источник для использования в брахитерапии, способ его изготовления (варианты), способ лечения с его использованием и композиция на его основе
US6471631B1 (en) 1998-11-27 2002-10-29 Syntheon, Llc Implantable radiation therapy device having controllable radiation emission
US6749554B1 (en) 1999-02-25 2004-06-15 Amersham Plc Medical tools and devices with improved ultrasound visibility
US6482143B1 (en) 1999-02-28 2002-11-19 Syntheon, Llc Raidoactive therapeutic seed having selective marker configuration
US6730013B1 (en) 1999-04-09 2004-05-04 Medi-Physics, Inc. Method and apparatus for loading delivery systems for brachytherapy seeds
US6066302A (en) 1999-04-28 2000-05-23 Bray; Lane A. Method of separation of Cesium-131 from Barium
WO2000064538A1 (fr) 1999-04-28 2000-11-02 Medi Physics, Inc. Produits et procedes de curietherapie
FR2797477B1 (fr) 1999-08-09 2001-10-12 Cit Alcatel Palier magnetique du type rotule pour corps basculant
ATE281873T1 (de) 1999-09-14 2004-11-15 Nucletron Bv Radioaktive brachytherapiequelle und material und herstellungsverfahren
US6403916B1 (en) 2000-05-12 2002-06-11 Isostar International, Inc. System and automated method for producing welded end closures in thin-walled metal tubes
US6479920B1 (en) 2001-04-09 2002-11-12 Wisconsin Alumni Research Foundation Direct charge radioisotope activation and power generation
US6471632B1 (en) 2001-05-18 2002-10-29 Syntheon, Llc Radioactive therapeutic seeds
EP1429345A1 (fr) 2002-12-10 2004-06-16 Ion Beam Applications S.A. Dispositif et procédé de production de radio-isotopes
EP1766635B1 (fr) 2004-06-28 2008-03-26 Isoray Medical, Inc. Procede de separation et purification du cesium 131 a partir du nitrate de baryum
CA2576907C (fr) 2004-07-28 2014-04-22 Isoray Medical, Inc. Procede de separation et de purification du cesium-131 a partir du carbonate de barium
US7316644B2 (en) 2004-08-18 2008-01-08 Isoray Medical, Inc. Method for preparing particles of radioactive powder containing Cesium-131 for use in brachytherapy sources

Patent Citations (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US3706689A (en) * 1968-05-03 1972-12-19 Nuclear Associates Inc Process for the preparation of a sr**90-y**90 beta source in a radiation hazard free manner
US5368736A (en) * 1993-07-26 1994-11-29 The United States Of America As Represented By The United States Department Of Energy Process for the separation and purification of yttrium-90 for medical applications
WO2001080251A2 (fr) * 2000-04-14 2001-10-25 Pg Research Foundation, Inc. Procede d'isolation et de purification de 90y provenant de 90 strontium en quantites multi-curies

Non-Patent Citations (1)

* Cited by examiner, † Cited by third party
Title
WIKE J S ET AL: "CHEMISTRY FOR COMMERCIAL SCALE PRODUCTION OF YTTRIUM-90 FOR MEDICAL RESEARCH", INTERNATIONAL JOURNAL OF RADIATION APPLICATIONS AND INSTRUMENTATION PART A: APPLIED RADIATION AND ISOTOPES, PERGAMON PRESS LTD., EXETER, GB, vol. 41, no. 9, January 1990 (1990-01-01), pages 861 - 865, XP000169509 *

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